ML18142A822
| ML18142A822 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/25/1977 |
| From: | White L Rochester Gas & Electric Corp |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18142A822 (5) | |
Text
NR1.'o"iM 195 I2.761
. ~NRC DISTRIBUTION roA PART 50 DO V.S. NUCLEAR ISEGVLATOBVCOMhIISSION CI(CT MATERIAL
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Mr. Ao Schwencer I'ROM:
Rochester Gas 8 Electric Corp Rochester, New York L,
D White, Jr DATE OF DOCUMENT 4/25/77 DATE RECEIVED 4/29/77
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] S) S]vs Ltr~ furnishing response to NRC request regarding the Ginna core baffleo ~ ~ ~ ~ ~ ~ ~
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o S9 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHITE, JR.
VICE PRESIDENT TCLEPHONC AecA coor. 7>o 546.2700 pqpulatOU F~t> egg April 25, 1977 Director of Nuclear Reactor Regulation Attention:
A. Schwencer, Chicf Operating Reactor Branch No.
1 U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
R.E. Ginna Nuclear Power Plant Unit No.
1 Docket. No. 50-244
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Dear Nr. Schwencer:
This letter is in response to a request from a member of the NRC Staff regarding the Ginna core baffle.
The leakage through the "Z" baffle joint at another plant has historically lead to fuel rod failures.
During the Ginna 1976 refueling, the fuel assemblies adjacent to the "Z" baffle joints during Cycle 5 were inspected with binoculars and no anomalies were found.
In addi-tion, the fuel assemblies adjacent to the "Z" baffle joints during the,. previous cycle (Cycle 4) were examined by binoculars and were leak tested.
The results of the leak testing support the conclu-sion that Ginna baffle does not have the baffle joint condition seen elsewhere.
Very truly yours, L. D. Whit
, Jr.
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S9 EAST AVENUE, ROCHESTER, N.Y. I4649 LEON D. WHITE, JR.
VICE PRESIOENT TELEPHONE AREA COOE TIE 546-2700 April 26, 1977 Director of Nuclear Regulation ATTN:
Mr. A. Schwencer, Chief Operating Reactors Branch gl U. S., Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Mr. Schwencer:
Your letter of April 1, 1977 requested that we implement procedures to prevent reactor coolant pump (RCP) starts while in the water solid condition or, in the event such starts could not be avoided, to include procedural steps to ensure that an acceptable reactor coolant system (RCS) temperature profile exists prior to starting a reactor coolant pump.
As discussed in our letter of February 24, 1977, there are times when reactor coolant pump starts are necessary while in the water solid condition.
Therefore we will revise our operating procedures to include non-optional prerequisite steps while in a water solid condition to determine the reactor coolant system temperature profile befoxe starting a reactor coolant pump.
Appropriate measures will be specified to achieve an acceptable profile prior to starting the pump.
In addition, we will conduct a review of our procedures to ensure that they are consistent with our February 24, 1977 submittal.
These procedural revisions and reviews will be completed prior to startup at the end of our present refueling and'main-tenance outage.
Sincerely,
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L. D. Whi e, Jr.
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